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EQUIPOISE 3A (open access)

EQUIPOISE 3A

None
Date: June 1, 1962
Creator: Nestor, C. W. Jr.
Object Type: Report
System: The UNT Digital Library
COMPILER INTO GEORGE ASSEMBLY ROUTINE (open access)

COMPILER INTO GEORGE ASSEMBLY ROUTINE

This program of the GEORGE Assembly Routine (GAR) will accept Fortran- like statements from paper tape and create the GAR language program on tape. This includes the needed calls for common subroutines and the reservations for the named variables and temporaries. The original statements in Fortran are carried along as remarks. The GAR language program may then be processed in the usual way by the GEORGE Assembly Routine, giving machine-language code. The level of sophistication of the source language is roughly equal to that of Fortransit or SALT. (auth)
Date: June 1, 1962
Creator: George, R.
Object Type: Report
System: The UNT Digital Library
Quarterly Status Report on LAMPRE Program for Period Ending May 20, 1962 (open access)

Quarterly Status Report on LAMPRE Program for Period Ending May 20, 1962

During the report period 110 Mw-hr of operation were completed by LAMPRE I at various power levels, and observations were made of control element performance and reactivity losses. Metallographic examination of a Core I capsule having 120 Mw-hr of irradiation exposure disclosed no major attack. Core II utilizes Ta alloy melts and 13 fuel melts. Starting materials for Core II capsules are tabulated. In research and development a gamma-ray conversion television was used to observe the flow of molten Pu in the PTA experiment. Dilute fuels being studied for use in a high-performance reactor include Pu --Co - -Ce alloys, ing exposure of test containers to U --Pu -Mn fuel at 900 deg C for 2 hrs are tabulated. In fuel reprocessing data on decontamination of Pu metal by electrorefining and by solvent extraction were obtained. Details of maintenance and development of the core test facility are included. (J.R.D.)
Date: June 1, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
FUEL CYCLE DEVELOPMENT PROGRAM. Quarterly Progress Report, January 1 to March 31, 1962 (open access)

FUEL CYCLE DEVELOPMENT PROGRAM. Quarterly Progress Report, January 1 to March 31, 1962

The permanent shutdown of the Westinghouse Testing Reactor at the end of the quarter forced a revision in plans for programming the remainder of the irradiation of the two uninstrumented capsules whose testing was in progress. The minimum estimated burnup at this point, based on hot cell data obtained from the pilot capsule, was 13,100 MW-d/ton U. It was decided to continue the testing of only one capsule in another reactor until the original goal of 20,000 MW-d/ton U is reached. The irradiation of the second capsule is to be terminated so that it can serve as a control. Fabrication was initiated on enriched UO/sub 2/ pellets for incorporation in full scale fuel rods to be irradiated in the Vallecitos Boiling Water Reactor. A wet nitrogen pyrohydrolysis step in conjunction with oxidationreduction cycling is being used to attain a satisfactory density exceeding 95% of theoretical at 1150 deg C. Apparatus and procedures being used for measurement of thermal conductivity and thermal expansion of sintered and cast uranium carbide are described. The coefficient of linear thermal expansion for a single specimen of 4.37 wt.% carbon sintered uranium carbide was determined to be 11.8 x 10/sup -6/ mm/mm- deg C, while that …
Date: June 1, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Chemical Technology Division, Unit Operations Section Monthly Progress Report, January 1962 (open access)

Chemical Technology Division, Unit Operations Section Monthly Progress Report, January 1962

None
Date: June 1, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Object Type: Report
System: The UNT Digital Library
FEASIBILITY OF Pu$sup 239$-U$sup 235$-FUELED CORES TO PREDICT Pu$sup 239$- FUELED CORE DIMENSIONS (open access)

FEASIBILITY OF Pu$sup 239$-U$sup 235$-FUELED CORES TO PREDICT Pu$sup 239$- FUELED CORE DIMENSIONS

Use of Pu/sup 239/ -- U/sup 235/-fueled fast critical assemblies to estimate properties of Pu/sup 239/-fueled assemblies is of interest because of safety considerations and limited plutonium availability. Bare and reflected homogeneous cores and reflected two-region cores are considered. The fuel, 5% by volume, is assumed to be Pu/sup 239/ and U/sup 235/ of various fuel composition ratios for the homogeneous cores. For the tworegion cores the 5% fuel volume is Pu/sup 235/ in the central region and U/sup 235/ in the outer core region. Core diluents, simulating fertile, structural, and coolant materials, are assumed identical in all cases. it is estimated that construction of the reflected two- region core with ratio of central core region volume to total core volume of 0.1 will theoretically decrease the calculated error in prediction of the critical size of a corresponding solely Pu/sup 239/-fueled assembly by a factor of about 10 to 20. (auth)
Date: June 1, 1962
Creator: Meneghetti, D. & Ishikawa, H.
Object Type: Report
System: The UNT Digital Library
ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART III. STAINLESS STEEL (304) IN NITRATE SOLUTIONS (open access)

ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART III. STAINLESS STEEL (304) IN NITRATE SOLUTIONS

The potential-current density relationships for 304 stainless steel dissolution in a nitrate system were studied as a function of solution composition and temperature in order to optimize the conditions for electrolytic dissolution of ihis material. In the nitrate system, the anodic dissolution of steel takes place in the transpassive region. Under some conditions, deviations from Tafel behavior are observed which depend greatly on the nitrate and hydrogen ion concentration, and on temperature. A discussion of passivity, transpassivity, secondary passivation, the limiting current density, and the effect of alloy composition on the dissolution behavior is given. It was found that at temperatures above 60 deg C efficient dissolver operation should be possible over a wide range of solution compositions and at current densities up to 2 amp/cm/sup 2/. (auth)
Date: June 1, 1962
Creator: Aylward, J. R. & Whitener, E. M.
Object Type: Report
System: The UNT Digital Library
ECONOMIC FACTORS OF MFP THERMOELECTRIC GENERATORS. Interim Report (open access)

ECONOMIC FACTORS OF MFP THERMOELECTRIC GENERATORS. Interim Report

Mixed Fission Products (MFP) for use as a heat source for thermoelectric generators will become increasingly available in the coming years. The Atomic Energy Conamission sponsored program on solidification of nuclear wastes is now entering the hot-bench scale test phase. During this phase approximately 5000 thermal watts of two year old MFP could be produced monthly. Two different types of hot calcination pilot plants are planned for installation at the Hanford National Laboratories in the 1964 to 1966 time period. Each of these plants should be able to produce 160,000 thermal watts of two year MFP and 16,000 thermal watts of ten year MFP on a monthly basis. During this phase, MFP costs should be less than 15 per ihermal watt for two year MFP and 50 for ten year MFP. This cost includes operation of the plant solely to obtain heat sources and sealing the MFP into fuel containers. A full scale plant for a 15,000 Mw(e) nuclear economy is estimated to produce four to five times as much MFP as either of the pilot plants. Costs will be dependent upon AEC policy in effect at the time the plant is operating. lf the policy indicates that the full …
Date: June 1, 1962
Creator: Barmat, M.
Object Type: Report
System: The UNT Digital Library
CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JANUARY-MARCH 1962 (open access)

CHEMICAL ENGINEERING DIVISION SUMMARY REPORT, JANUARY-MARCH 1962

Additional experiments conducted on nitridation of irradiated U-fissium fuel pins revealed that irradiation does not greatly affect the nitridation rate at 300 deg C. In skullreclamation development, a phase separation common to both the blanket- and skull-processes was investigated in which a 50% Mg-- Zn supernatant solution was removed from precipitated U metal. In most runs the supernatant phase was removed with negligible U entrainment. The reduction rate of ZrO by Zn--Mg solution under skull-recovery process conditions was found to be lower than that of U oxides. It may be possible in this process to effect some Zr separation by limiting the reduction time to that necessary for U. Methods of procesging EBR-II fuels are being investigated to establish methods of separating rare earths from Pu. Development work on preparation of UC by addition of C to U dissolved in liquid metal media showed that the limited addition of alkali metals improves C wetting and the tests showod high C-to-U ratios and high O/sub 2/ contamination; procedure and equipment improvements are being made. Studies are in progress to evaluate the compatibility of various materials with the liquid metal-salt systems contemplated for reactor fuel reprocessing. Tungsten appears to have high corrosion …
Date: June 1, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Irradiation Behavior of Restrained and Vented Uranium-2 w/o Zirconium Alloy. Final Report-Programs 6.1.22 and 6.1.27 (open access)

Irradiation Behavior of Restrained and Vented Uranium-2 w/o Zirconium Alloy. Final Report-Programs 6.1.22 and 6.1.27

Twelve 0.22-in.-diameter fuel specimens containing a longitudinal central vent and clad with 0.010 in. of Type 304 stainless steel were irradiated to evaluate the effect of restraint and a central vent on fuel element stability. The cladding of 10 of the specimens contained porous end plugs to vent any released fission gas and thus to minimize the buildup of gas pressure within the stainless steel cladding. The specimens consisted of a 20% enriched uranium--2 wt% zirconium alloy core surrounded by a natural uranium--2 wt% zirconium alloy sleeve. Eight of the specimens were irradiated to burnups of the enriched core of 6.9 to 12.8% of all atoms (1.2 to 2.2 at.% of the duplex assembly) at maximum fuel temperatures ranging from 280 to 760 deg C. Most of the clad specimens exhibited negligible volume increases as a result of irradiation. Two specimens containing central vents but unclad were irradiated together with the clad specimens in an attempt to differentiate between the effects due to a central vent and the effects due to cladding. The central vent in itself did not appear to reduce the swelling characteristics of the alloy. Mechanical restraint appeared to have extended the useful operating temperatures of the …
Date: June 1, 1962
Creator: Horak, J. A.; Kittel, J. H. & Yaggee, F. L.
Object Type: Report
System: The UNT Digital Library
The Generation of Poisson Time Distributed Random Pulses (open access)

The Generation of Poisson Time Distributed Random Pulses

The need for a source of pulses randomly distributed in time according to the Poisson distribution is discussed. A theoretical analysis showed that these pulses may be generated by employing an electrical white noise'' source. Calculations indicated the feasibility of a generator capable of producing Poisson pulse at a maximum average rate of one megacycle. The results of laboratory experiments support the calculations and demonstrate the nadequacy of using periodic pulses to determine instrument response to random pulses. A design of a nuclear signal simulator incorporating the Poisson pulse generator is suggested. (auth)
Date: June 1, 1962
Creator: Wilde, N.
Object Type: Report
System: The UNT Digital Library

[Photograph 2012.201.B0250.0924]

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "MOVING INTO FINAL qualifying play for the U.S. Open golf tournament this week are Oklahoma State golf coach Labron Harris, right, and his son, Labron Jr."
Date: June 1, 1962
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0260.0354]

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "Two bridges to replace the old Newcastle bridge over the South Canadian river on U. S. 62-277 south of Oklahoma city are about 80 percent complete."
Date: June 1, 1962
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0311.0064]

Photograph taken for a story in the Daily Oklahoman newspaper. Caption: "Jean is a newcomer to the local bowling scene, having come to Oklahoma City only six weeks ago from the Philippines where she had wound up the winter season bowling in four leagues."
Date: June 1, 1962
Creator: Cobb, Richard
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0116.0044]

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "For Clarence A. Burg, dean of Okla. City Univ. school of music, senior commencement this year is his commencement too-or perhaps more accurately--his re-commencement."
Date: June 1, 1962
Creator: King, Cliff
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0116.0053]

Photograph used for a story in the Oklahoma Times newspaper. Caption: "Dr. Clarence Burg, dean emeritus of Oklahoma City University's School of Music, is a firm believer that one's usefulness to his profession need not end with his retirement."
Date: June 1, 1962
Creator: King, Cliff
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0122.0339]

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "The old Canadian County courthouse, built 60 years ago, is one of the finest examples of early Oklahoma architecture."
Date: June 1, 1962
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0089.0007]

Photograph used for a newspaper owned by the Oklahoma Publishing Company.
Date: June 1, 1962
Creator: unknown
Object Type: Photograph
System: The Gateway to Oklahoma History

[Photograph 2012.201.B0122.0340]

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "In the early stages of construction. The picture was taken from under the entrance of the old courthouse, left."
Date: June 1, 1962
Creator: Garner, Frank
Object Type: Photograph
System: The Gateway to Oklahoma History
CHARACTERIZATION OF THE PHOTOSYNTHETICALLY SYNTHESIZED 'gamma-KETOACID' PHOSPHATE AS A DIPHOSPHATE ESTER OF 2-KETO-L-GULONIC ACID (open access)

CHARACTERIZATION OF THE PHOTOSYNTHETICALLY SYNTHESIZED 'gamma-KETOACID' PHOSPHATE AS A DIPHOSPHATE ESTER OF 2-KETO-L-GULONIC ACID

The summary of this report is that a substance isolated from Chlorella Pyrenoidosa metabolizing {sup 14}CO{sub 2} in the light, previously believed to be a diphosphate ester of a 2-carboxy-4-pentulose, has now been shown to be a disphosphate of 2-keto-L-gulonic acid. The phosphate groups appear to be attached to two of the carbon atoms 3-6. Evidence is presented suggesting that this compound arises from glucose, or a glucose phosphate, which is not in rapid equilibrium with photosynthetically produced glucose derivatives.
Date: June 1, 1962
Creator: Moses, V.; Ferrier, R.J. & Calvin, M.
Object Type: Report
System: The UNT Digital Library
Honey Grove Signal-Citizen (Honey Grove, Tex.), Vol. 72, No. 21, Ed. 1 Friday, June 1, 1962 (open access)

Honey Grove Signal-Citizen (Honey Grove, Tex.), Vol. 72, No. 21, Ed. 1 Friday, June 1, 1962

Weekly newspaper from Honey Grove, Texas that includes local, state, and national news along with advertising.
Date: June 1, 1962
Creator: Morrow, Joe T.
Object Type: Newspaper
System: The Portal to Texas History
The Brady Standard and Heart O' Texas News (Brady, Tex.), Vol. 53, No. 33, Ed. 1 Friday, June 1, 1962 (open access)

The Brady Standard and Heart O' Texas News (Brady, Tex.), Vol. 53, No. 33, Ed. 1 Friday, June 1, 1962

Weekly newspaper from Brady, Texas that includes local, state, and national news along with advertising.
Date: June 1, 1962
Creator: Smith, L. B.
Object Type: Newspaper
System: The Portal to Texas History
The Clarksville Times (Clarksville, Tex.), Vol. 90, No. 20, Ed. 1 Friday, June 1, 1962 (open access)

The Clarksville Times (Clarksville, Tex.), Vol. 90, No. 20, Ed. 1 Friday, June 1, 1962

Weekly newspaper from Clarksville, Texas that includes local, state, and national news along with advertising.
Date: June 1, 1962
Creator: Pinson, Joe
Object Type: Newspaper
System: The Portal to Texas History
The Comanche Chief (Comanche, Tex.), Vol. 88, No. 49, Ed. 1 Friday, June 1, 1962 (open access)

The Comanche Chief (Comanche, Tex.), Vol. 88, No. 49, Ed. 1 Friday, June 1, 1962

Weekly newspaper from Comanche, Texas that includes local, state, and national news along with advertising.
Date: June 1, 1962
Creator: Wilkerson, J. C.
Object Type: Newspaper
System: The Portal to Texas History